ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Jae Ho Yang, Ki Won Kang, Kun Woo Song, Chan Bock Lee, Youn Ho Jung
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 113-119
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3518
Articles are hosted by Taylor and Francis Online.
Techniques to fabricate thorium-uranium dioxide fuel [(Th,U)O2] have been developed, and the thermal conductivity of (Th,U)O2 pellets has been measured. Mixtures of thorium dioxide (ThO2) and uranium dioxide (UO2) powders were successfully wet-milled, compacted, and sintered at 1700°C to fabricate (Th,U)O2 pellets. The wet-milling process results in a fuel density of 96 to 98% of theoretical density and a uniform distribution of the uranium and thorium in the (Th,U)O2 pellet. The laser flash method was used to measure the thermal diffusivity of the ThO2 and (Th,U)O2 pellets, and the thermal conductivities of (Th0.655U0.345)O2 and (Th0.355U0.645)O2 fuel were found to be lower than that of ThO2 or UO2 fuel. The degradation of the thermal conductivity by the UO2 substitution is great at low temperatures but decreases as the temperature increases.